ML20138C768
| ML20138C768 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 10/11/1985 |
| From: | Massin H COMMONWEALTH EDISON CO. |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20138C772 | List: |
| References | |
| 0761K, 761K, NUDOCS 8510230036 | |
| Download: ML20138C768 (4) | |
Text
7 r~N Commonwealth Edison 2
one Fwst Nation 11 Plua. Chicago, libnois O 'J Address R ply to: Post Office Box 707 gj Chicago, lihnois 60690.
October 11, 1985 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC 20555
Subject:
' LaSalle County Station Unit 1 Proposed Amendment to Technical Specification for Facility Operating License PPF-ll ECCS/RCIC Testable Check Bypass Valves tRC Docket-Nos. 50-373-References (a): P&ID M-95, HPCS - Vol. X, UFSAR.
(b): UFSAR Table 6.2-21.
(c): P&ID M-101, RCIC - Vol..X, UFSAR.
(d): FSAR Question 212.48.
(e): SSER-2 Section 6.3.4.
(f): Unit 1 Pump and Valve Inservice Inspection Program.
(g): Unit 2 Pump and Valve Inservice Inspection Program.
Dear Mr. Denton:
Pursuant to 10 CFR 50.59, Commonwealth Edison proposes to amend Appendix A, Technical Specification, to Facility Operating License tPF-ll.
These changes are being submitted for your staff's review and approval.
Attachment A provides background ano discussion. The proposed change is enclosed in Attachment B.
The attached change has received both On-Site and Off-Site review and approval. We have reviewed this amendment request and find that no significant hazards consideration exists. Our review is documented in Attachment C.
Conrnonwealth Edison is notifying the State of Illinois of our request for this amendment by transmitting a copy of this letter and its P
attachments to the designated State Official.
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H. R. Denton October 11, 1985 The modification to remove these valves will.De performed during the first refueling outage and the amendment must be approved before startup for Cycle 2.
This is currently scheduled for March, 1985. Removing these valves makes Unit 1 look like Unit 2, which is a human factors concern, and it also removes a high-low pressure interface leakage path concern.
In accordance with the requirements of 10 CFR 50.170, a fee remittance in the amount of $150.00 is enclosed.
Please direct any questions you may have concerning this matter to this office.
Three (3) signed originals and thirty-seven (37) copies of this transmittal and its attachments are provided for your use.
Very truly yours,
@tW d H. L. Massin Nuclear Licensing Administrator im Attachments A: Background and Discussion 8:
Technical Specification Change to iPF-11 C: Evaluation of Significant Hazards Consideration cc: Region III Inspector - LSCS A. Bournia - NRR M. Parker - State of Ill SUBSCRIBE 0 AND SWOg4 to
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I ATTACHMENT A TECHNICAL S'ECIFICATION CHANGE REQUEST LASALLE COUNTY STATION UNIT 1 ECCS/RCIC TESTABLE CHECK BYPASS W.LVES BACKGROUND Each ECCS/RCIC injection line into the reactor vessel has an air operated testable check valve installed inside the primary containment (reference (a) - HPCS).
(The arrangement for RCIC is one testable check valve inside and one outside the primary containment - reference (c)).
The valves are installed to prevent loss of reactor inventory in the event the injection line breaks between the check valve and the motor operated injection gate valve. These valves also perform a high to low pressure interface isolation function (reference (e)). Since these valves are in the injection flow path, they must be periodically exercised and are therefore incluoed in the Pump and Valve Inservice Inspection Program per ASME Section XI (reference (f)).
At the time of LaSalle County Station's design, it was expected that these valves would be required to be exercised while the reactor was at pressure. To meet this requirement an air operated bypass valve was installed around the check valve to equalize the pressure across the check valve disk 'arx1 thus allowing the check valve air operator to exercise the check valve. This bypass valve is a 3/4 inch globe valve (reference (d)).
In addition, to ensure this valve would not be open during a LOCA, an isolation signal from low water level and high drywell pressure (Group 2) m was added (reference (b)) and included in the Technical Specifications.
DISCUSSION The original Unit 1 Inservice Inspection program was submitted with testable check valves IE12-F041 A,B,C (LPCI) and IE21-F006 (LPC5) to be exercized during cold shutdown only, with IE22-F005 (H'CS), lE51-F065 (RCIC), and 1E51-F066 (RCIC) to be exercised quarterly. This plan was submitted in October 1980.
An updated Inservice Inspection program was submitted in February 1983 for Unit 1.
In this plan all the ECCS/RCIC testable check valves listed above were specified to be exercised during cold shutdown.
The Unit 2 Program was submitted in November 1983 (reference (g)).
This plan also listed the testable check valves for cold shutdown exercising only.
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. t During power operation these testable check valves have a differential pressure across them of approximately 1000 psid. To ensure that no potential to overpressurize the low pressure piping exists, these valves are leak tested per Technical Specification 4.4.3.2.2 in addition to the motor operated injection gate valves. Because of this potential the valves snould not be cycled during pressurized conditions to maintain double valve protection for the low pressure piping. (See reference (e)). For this reason the Unit 2 testable check valves did not have bypass valves installed around them. The Unit 2 Technical Specifications were issued without including the testable check bypass valves.
CONCLUSION Commonwealth Edison believes that the bypass valves are not required for safe plant operation. These valves will be deleted from the Unit 1 LSCS Technical Specifications as indicated on Attachment A.
These valves are scheduled to be removed from the Unit 1 ECCS/RCIC injection lines at the first refueling outage. Required changes to the UFSAR will be made and submitted with the next amendment following the modifications. The Pump and Valve Inservice Inspection Programs for the testable check valves will be updated following the modification.
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